ML13330A774
| ML13330A774 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/31/1979 |
| From: | Head J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7910050275 | |
| Download: ML13330A774 (6) | |
Text
Southern California Edison Company P. O. BOX bOO 2244 WALNUT GROVE AVENUE J.
T.
H1 EAD0, JR.
ROSEMEAD, CALIFORNIA 91770 TELEPHONE August 31, 1979 213-5721472 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V Suite 202, Walnut Creek Plaza 1990 North California Boulevard Walnut Creek, California 94596 Attention:
Mr. R. H. Engelken, Director Docket No.
50-206 San Onofre Unit 1
References:
(1) SCE (J.T. Head, Jr.) to NRC (R.H. Engelken) dated April 19, 1979, Docket 50-206 (2) SCE (J.H. Drake) letter to NRC (R.H. Engelken) dated May 3, 1979, Docket No. 50-206 (3) SCE (J.T. Head, Jr.) letter to NRC (R.H. Engelken) dated May 23, 1979, Docket No. 50-206 (4) SCE (J. T. Head, Jr.) letter to NRC (R. H. Engelken) dated June 25, 1979, Docket 50-206 (5) NRC (D. L. Ziemann) letter to SCE (J. H. Drake) dated August 7, 1979, Docket 50-206 References (1),
(2) and (3) provided our responses to IE Bulletin 79-06A and Revision 1 thereto which requested information concerning the Three RIle Island Incident. References (1) and (2) addressed IE Bulletin Items 1-12 while Reference (3) addressed IE Bulletin Item 13 and provided schedular information for completing the outstanding action items identified in References (1) and (2).
Reference (4) provided additional information to supplement our responses submitted by References (1),
(2) and (3).
(lq rmSO~l}s
-2 The purpose of this letter is to provide updated schedular information for outstanding action items identified in References (1),
(2) and (4).
The original schedular information was provided by references (3) and (4).
To facilitate your review, the updated schedules have been consolidated from the above references and are cross referenced to the IE Bulletin action items in the enclosed Table 1.
Outstanding items 4 and 7 require plant specific input from our reactor supplier (Westinghouse) prior to completion. Schedules for these items have been extended to reflect the most recent Westinghouse proposals.
Westinghouse has indicated that the abnormal workload related to Three Mile Island and the large amount of plant specific work which must be accomplished for San Onofre Unit 1 have been the prominent factors in the -extended schedules.
Outstanding items la and 3a also require input from Westinghouse.
However, this input is predominantly generic in nature and has therefore been incorporated into the Work Scope of the Westinghouse TMI Owners Group.
Schedules for these items have not yet been formalized, but will be made available to you when they are developed.
The procedure changes we are making to complete our action on Outstanding Items 9 and 10 are in the final review stages. A summary of these changes will be submitted as requested by Reference (5).
Should you have any questions or require additional information, do not hesitate to contact me.
Sincerely, Enclosure cc:
Director, Office of Inspection and Enforcement Division of Reactor Operations Inspection
bcc:
J.E. Thomas (SDG&E)
R.L. Erickson (SDG&E)
D.R. Pigott (Chickering & Gregory)
O.J. Ortega/J.H. Drake A. A. Arenal J.T. Head, Jr.
R.S. Currie H.L. Ottoson J.M. Curran B.L. Curtis R.R. Brunet J.R. Tate C.R. Kocher/J.A. Beoletto K.P. Baskin D.E. Nunn J.G. Haynes W.C. Moody G.T. McLandrich R.W. Krieger/P.H. Penseyres J.L. Rainsberry NRC Files EDM Files J. Signorelli (NUS)
-4 TABLE 1 Outstanding Action Items Per IE Bulletin 79-06A Rev. 1 IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Reference Date
- 1. a) Review design basis accidents Item 1 Incorporated into and transients to identify Westinghouse TMI conditions wherein pressurizer Owners Group. No level may not be indicative of schedule at this time.
reactor vessel level.
b) Revise operating instructions Item 1 One month after as appropriate based on appraisal completion of la above of above review.
- 2. Review emergency instructions to Item 1 Completed insure that the actions to be taken by operators as specified in those instructions are consistent with Station Order S-0-104.
- 3.
a)
Determine potential for void Item 2 Incorporated into formation and methods for Westinghouse TMI operator recognition and Owners Group. No prevention, schedule at this time.
b)
Revise operating instructions Item 2 One month after based on appraisal of above completion of la above review to:
(i) assure that action steps specifically warn of potential for voiding with a description of all instrumentation which might provide indication of potential or actual voiding, (ii) specifically address operator actions, based on operational modes and instrument indication discussed above, for terminating conditions tending to lead to void formation and (iii) provide operators with guidance for enhancing core cooling given the unexpected conditions of actual voiding in primary system.
IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Reference Date c) Provide a summary of the results of Item 2 Two weeks after the review (Item 3a) and subsequent completion of the procedure revisions (Item 3b).
review.
d) Provide station operators with Item 2 Completed interim information-regarding instrumentation available to detect core voiding and verify natural circulation.
- 4. Review design change implementing NRC Item 3 October 31, 1979 directive concerning pressurizer level/S.I.S. actuation in accordance with the Technical Specifications and 10CFR 50.59.
- 5. Revise operating procedures to require Item 4 Completed manual actuation of all automatic containment isolation valves in the event of automatic initiation of safety injection.
- 6. When relief from the requirement Item 5 Upon receipt of NRC for a standby operator is granted from approval for NRC, revise emergency operating deletion of the instructions to effect timely manual standby operator initiation of auxiliary feedwater requirement.
following transients and accidents.
- 7.
Evaluate ability of PORV isolation Item 6 October 31, 1979 valve to close with PORV wide open at design temperature and pressure.
- 8.
Review emergency operating Item 7 Completed instructions to identify and resolve any conflicts with the safety injection termination criteria.
- 9.
a) Review positioning requirements Item 8 August 28, 1979 and positive controls for engineered safeguard features valves and revise procedures as required.
b) Provide a summary of the results Item 8 August 28, 1979 of the review and any procedural revisions to NRC.
-6 IE Bulletin 79-06A Scheduled Completion Item Description Rev. 1 Reference Date
- 10. a) Review administrative controls Item 10 August 28, 1979 for maintenance and testing of safety-related systems to verify operability of redundant safety-related systems prior to removal from service and to ensure operability upon return to service. Revise procedures as required.
~~ cf' t~
~
~ A~ut ur-rfl ugst z, of the review and any procedural revisions (Item 10(a)) to NRC.
- 11. Install an additional telephone Item 11 Completed circuit to provide a continuous open communication channel with NRC following prompt reportable occurrences.
- 12. Revise operating procedures Item 12 Completed to provide appropriate action for hydrogen control.
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